Philippe Spaetig

Nationalité: swiss

Mission

Évaluation de l'intégrité des internes des réacteurs nucléaires et des composants du système de refroidissement primaire, ainsi que de la fragilisation des aciers des cuves sous pression.
Développement de techniques d'essai sur petits échantillons, de méthodes non destructives et d'analyses analytiques et numériques pour déterminer l'évolution des propriétés des matériaux dans des environnements difficiles.
Enseignement dans le cadre du master en génie nucléaire et formation de jeunes scientifiques dans le domaine des matériaux et des combustibles nucléaires.
Philippe Spätig est actuellement professeur adjoint à l'EPFL à l'École des sciences fondamentales, au Laboratoire de physique des réacteurs et de comportement des systèmes. Il a obtenu son diplôme d'ingénieur physicien à l'EPFL en 1991 et son doctorat à l'EPFL en 1995 sur le rôle de l'activation thermique dans la plasticité de l'intermétallique Ni3Al.
De 1995 à 1997, il a travaillé comme post-doctorant au sein du groupe Matériaux du Centre de recherche en physique des plasmas de l'EPFL, où il a étudié les effets de l'irradiation par protons à haute énergie sur les alliages et les métaux purs. Il a ensuite rejoint l'université de Californie à Santa Barbara et a passé deux ans dans le groupe du professeur G.R. Odette, où il a travaillé sur la mécanique de la rupture des aciers ferritiques de construction.
Il a rejoint à nouveau le groupe Matériaux du Centre de recherche en physique des plasmas de l'EPFL en 2000 et a travaillé dans ce groupe jusqu'à la fin de 2012. Ses recherches ont porté sur le durcissement et la fragilisation des aciers sous irradiation, ainsi que sur le développement d'aciers renforcés par dispersion d'oxydes. Il a également travaillé et développé des techniques expérimentales et analytiques d'essai sur petits échantillons afin d'extraire de manière fiable les propriétés mécaniques d'un volume limité de matériau.

En 2013, il a rejoint le Laboratoire des matériaux nucléaires de l'Institut Paul Scherrer, tout en restant affilié au Laboratoire de physique des réacteurs et de comportement des systèmes de l'EPFL. Depuis lors, il travaille principalement sur la fatigue et la rupture assistées par l'environnement des aciers austénitiques et des aciers pour cuves sous pression, où il étudie les effets de l'environnement des réacteurs à eau légère sur les propriétés mécaniques.

Formation

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1991 – 1991 EPFL - Switzerland

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1995 – 1995 EPFL - Switzerland
Dirigée par Prof. J.-L. Martin

Development of a crack arrest toughness measurement technique using small specimens to evaluate the fracture behavior in the ductile-brittle transition of "ferritic" steels

P. Gao

Lausanne, EPFL, 2025. DOI : 10.5075/epfl-thesis-10989.

EBSD and TKD for Multiscale Crystallography of Shape Memory Alloys

J. Xiao

Lausanne, EPFL, 2025. DOI : 10.5075/epfl-thesis-11538.

Fracture Toughness Evaluation of Inhomogeneous Reactor Pressure Vessel Steels Using Sub-sized Specimens

D. Jiang

Lausanne, EPFL, 2025. DOI : 10.5075/epfl-thesis-10963.

Effect of temperature on apparent crack arrest toughness of Eurofer97 measured by a newly developed small specimen test technique

P. GaoP. Spatig

Journal of Nuclear Materials. 2024. DOI : 10.1016/j.jnucmat.2024.155222.

Study of the irradiation hardening of a Fe9Cr ferritic model alloy by nanoindentations

D. ZhouP. SpatigQ. HayatP. SongN. Jennett  et al.

Nuclear Materials and Energy. 2024. DOI : 10.1016/j.nme.2024.101667.

On the determination of the reference temperature T0 of the Master-Curve method using subsized compact tension specimens

D. ZhouD. JiangP. SpätigH.-P. Siefert

Procedia Structural Integrity. 2024. DOI : 10.1016/j.prostr.2023.12.044.

Domain Imaging and Switching Dynamics in BaTiO3-Based Photonic Integrated Devices

J. Geler Kremer

Lausanne, EPFL, 2023. DOI : 10.5075/epfl-thesis-10308.

Microscopic Digital Image Correlation Analysis of Strain Distributions in Stainless Steel 316L Induced by Multiaxial Cyclic Loading

E. C. Kursun

Lausanne, EPFL, 2023. DOI : 10.5075/epfl-thesis-10202.

Design, prototyping, and thermo-mechanical modelling of a neutron spallation target impacted by high-energy proton-beam pulses in the n_TOF facility at CERN

R. Esposito

Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-8370.

Insights into hardening, plastically deformed zone and geometrically necessary dislocations of two ion-irradiated FeCrAl(Zr)-ODS ferritic steels: A combined experimental and simulation study

P. SongK. YabuuchiP. Spaetig

Acta Materialia. 2022. DOI : 10.1016/j.actamat.2022.117991.

Optical spectroscopy of earth-abundant zinc pnictides for photovoltaics

E. Z. Stutz

Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-8873.

Protein Engineering for Personalized therapy and diagnosis

L. Wei

Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-8705.

Role of mean stress on fatigue behavior of a 316L austenitic stainless steel in LWR and air environments

W. ChenP. SpatigH. P. Seifert

International Journal Of Fatigue. 2021. DOI : 10.1016/j.ijfatigue.2020.106111.

Characterization of Austenitic Stainless Steels with Regard to Environmentally Assisted Fatigue in Simulated Light Water Reactor Conditions

M. BruchhausenG. DundulisA. McLennanS. ArrietaT. Austin  et al.

Metals. 2021. DOI : 10.3390/met11020307.

Mean Stress Effect on the Fatigue Life of 304L Austenitic Steel in Air and PWR Environments Determined with Strain- and Load-Controlled Experiments

P. SpatigJ.-C. Le RouxM. BruchhausenK. Mottershead

Metals. 2021. DOI : 10.3390/met11020221.

First observation of spalling in tantalum at high temperatures induced by high energy proton beam impacts

C. Torregrosa MartinN. SolieriE. FornasiereJ. Busom DescarregaM. Calviani  et al.

European Journal of Mechanics - A/Solids. 2020. DOI : 10.1016/j.euromechsol.2020.104149.

Dynamic study of contact damping in martensitic stainless steels using nano-indentation

R. MouginotP. SpatigH.-P. Seifert

Mechanics Of Materials. 2020. DOI : 10.1016/j.mechmat.2020.103541.

Round Robin into Best Practices for the Determination of Indentation Size Effects

A. Ruiz-MorenoP. HähnerL. KurpaskaJ. JagielskiP. Spätig  et al.

Nanomaterials. 2020. DOI : 10.3390/nano10010130.

Post-irradiation examination of refractory metal candidates for antiproton targets at the European Laboratory for Particle Physics (CERN)

E. Fornasiere

Lausanne, EPFL, 2020. DOI : 10.5075/epfl-thesis-7542.

Experimental evaluation and modeling of fatigue of a 316L austenitic stainless steel in high-temperature water and air environments

W. Chen

Lausanne, EPFL, 2020. DOI : 10.5075/epfl-thesis-7831.

Evaluation of Quasi-Static and Dynamic Fracture Toughness on the Low-Alloy Reactor Pressure Vessel Steel JRQ in the Transition Region

P. SpätigV. MazánováS. SumanH. P. Seifert

2019. 18th International Conference on Fracture and Damage Mechanics. p. 294 - 299. DOI : 10.4028/www.scientific.net/KEM.827.294.

Environmental degradation of fracture resistance in high-temperature water environments of low-alloy reactor pressure vessel steels with high sulphur or phosphorus contents

Z. QueH. SeifertP. SpätigJ. HolzerA. Zhang  et al.

Corrosion Science. 2019. DOI : 10.1016/j.corsci.2019.04.011.

Effect of dynamic strain ageing on environmental degradation of fracture resistance of low-alloy RPV steels in high-temperature water environments

Z. QueH. SeifertP. SpätigA. ZhangJ. Holzer  et al.

Corrosion Science. 2019. DOI : 10.1016/j.corsci.2019.03.013.

Mean Stress Effect on Fatigue Behavior of Austenitic Stainless Steel in Air and LWR Conditions

W. ChenP. SpätigH. P. Seifert

Mechanical Fatigue of Metals; Springer, Cham, 2019.

Ferritic and Tempered Martensitic Steels

P. SpätigJ.-C. ChenG. R. Odette

Structural alloys for nuclear energy applications; Elsevier, 2019. p. 485 - 527.

High-Temperature Water Effects on the Fracture Behaviour of Low-Alloy Reactor Pressure Vessel Steels

Z. Que

Lausanne, EPFL, 2019. DOI : 10.5075/epfl-thesis-9391.

Stress relaxation in the presence of sudden strain bursts: Methodology and stress relaxation data of microcast aluminium microwires

S. VerheydennL. DeillonA. Mortensen

Data In Brief. 2018. DOI : 10.1016/j.dib.2018.11.047.

Evaluation of mechanical properties of irradiated zirconium alloys in the vicinity of the metal-oxide interface

A. W. ColldeweihA. BarisP. SpätigS. Abolhassani

Materials Science and Engineering:. 2018. DOI : 10.1016/j.msea.2018.09.107.

Evolution of the tensile properties of the tempered martensitic steel Eurofer97 after spallation irradiation at SINQ

S. KnitelP. SpätigT. YamamotoH. SeifertY. Dai  et al.

Nuclear Materials and Energy. 2018. DOI : 10.1016/j.nme.2018.09.002.

Influence of mean stress and light water reactor environment on fatigue life and dislocation microstructures of 316L austenitic steel

P. SpätigM. HeczkoT. KrumlH.-P. Seifert

Journal of Nuclear Materials. 2018. DOI : 10.1016/j.jnucmat.2018.05.064.

Deformation twinning in irradiated ferritic/martensitic steels

K. WangY. DaiP. Spätig

Journal of Nuclear Materials. 2018. DOI : 10.1016/j.jnucmat.2018.01.057.

Helium effects on irradiation assisted stress corrosion cracking susceptibility of 316L austenitic stainless steel

I. Villacampa Roses

Lausanne, EPFL, 2018. DOI : 10.5075/epfl-thesis-8268.

Investigations and numerical modeling of mechanical properties of tempered martensitic steel Eurofer97 at various loading rates, temperatures and after spallation irradiation

S. Knitel

Lausanne, EPFL, 2018. DOI : 10.5075/epfl-thesis-8535.

Thermal activation parameters of plastic flow reveal deformation mechanisms in the CrMnFeCoNi high-entropy alloy

G. LaplancheJ. BonnevilleC. VarvenneW. A. CurtinE. P. George

Acta Materialia. 2018. DOI : 10.1016/j.actamat.2017.10.014.

Effect of residual stresses on notch toughness of the tempered martensitic steel F82H-MOD

N. IlchukV. DavydovP. SpätigH.-P. Seifert

Theoretical and Applied Fracture Mechanics. 2017. DOI : 10.1016/j.tafmec.2017.05.023.

Helium effects on IASCC susceptibility in as-implanted solution annealed, cold-worked and post-implantation annealed 316L steel

I. VillacampaJ. C. ChenP. SpätigH. P. SeifertF. Duval

Corrosion Engineering, Science and Technology. 2017. DOI : 10.1080/1478422X.2017.1323709.

Strength and fracture of silicon second-phase particles in aluminium casting alloys

M. G. Mueller

Lausanne, EPFL, 2017. DOI : 10.5075/epfl-thesis-7892.

Microstructure and tensile properties of ODS ferritic steels mechanically alloyed with Fe 2 Y

J. Macías-DelgadoT. LegueyV. De CastroM. AugerM. Monge  et al.

Nuclear Materials and Energy. 2016. DOI : 10.1016/j.nme.2016.09.019.

Physics-based constitutive modelling for crystal plasticity finite element computation of cyclic plasticity in fatigue

N. Grilli

Lausanne, EPFL, 2016. DOI : 10.5075/epfl-thesis-7251.

An inverse method based on finite element model to derive the plastic flow properties from non-standard tensile specimens of Eurofer97 steel

S. KnitelP. SpätigH. P. Seifert

Nuclear Materials and Energy. 2016. DOI : 10.1016/j.nme.2016.06.017.

Effect of high-temperature water and hydrogen on the fracture behavior of a low-alloy reactor pressure vessel steel

S. RoychowdhuryH. P. SeifertP. SpätigZ. Que

Journal of Nuclear Materials. 2016. DOI : 10.1016/j.jnucmat.2016.05.033.

Hardening induced by radiation damage and helium in structural materials

C. Vieh

Lausanne, EPFL, 2015. DOI : 10.5075/epfl-thesis-6490.

Embrittlement induced by the synergistic effects of radiation damage and helium in structural steels

K. Wang

Lausanne, EPFL, 2015. DOI : 10.5075/epfl-thesis-6824.

Measurement of residual stresses around the notch of tensile specimens of the high-Cr tempered martensitic steel F82H-mod

N. IlchukP. SpätigV. DavydovS. van Petegem

2014. 7th International Conference on Materials Structure and Micromechanics of Fracture (MSMF 7), Brno, CZECH REPUBLIC, JUL 01-03, 2013. p. 295 - 298. DOI : 10.4028/www.scientific.net/KEM.592-593.295.

Measurement of residual stresses around the notch of tensile specimens of the high-Cr tempered martensitic steel F82H-mod

N. IlchukP. SpätigV. DavydovS. van Petegem

2014. p. 295 - 298.

Investigation of microstructure and microhardness of pure W and W-2Y(2)O(3) materials before and after ion-irradiation

M. BattabyalP. SpätigB. S. MurtyN. Baluc

International Journal Of Refractory Metals & Hard Materials. 2014. DOI : 10.1016/j.ijrmhm.2014.06.004.

Analytical determination of the constitutive behavior from micro-pillar testing: Application to a tempered martensitic steel

N. IlchukP. SpätigH.-P. Seifert

Aip Advances. 2014. DOI : 10.1063/1.4873155.

Characterization and modeling of neutron irradiation, pre-deformation and warm prestressing effects on the fracture behavior of the tempered martensitic steel Eurofer97

N. Ilchuk

Lausanne, EPFL, 2013. DOI : 10.5075/epfl-thesis-5867.

Interaction between liquid aluminium and solid iron Al-rich intermetallics formation

G. Pasche

Lausanne, EPFL, 2013. DOI : 10.5075/epfl-thesis-6044.

On determination of the constitutive behavior of tempered martensitic steels from micro-indentations: Application to Eurofer97 steel

P. SpätigN. Ilchuk

Journal of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2013.01.003.

Fracture toughness characterization in the lower transition of neutron irradiated Eurofer97 steel

N. IlchukP. SpätigG. R. Odette

Journal of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2013.01.002.

Modelling oriented investigations of primary radiation damage in ultra high purity Fe and FeCr alloys

A. Prokhodtseva

Lausanne, EPFL, 2013. DOI : 10.5075/epfl-thesis-6008.

Microstructure and mechanical properties of a W-2wt.%Y2O3 composite produced by sintering and hot forging

M. BattabyalR. SchäublinP. SpätigM. WalterM. Rieth  et al.

Journal Of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2013.01.301.

Helium embrittlement of a lamellar titanium aluminide

P. MagnussonJ. ChenP. JungT. SauvageW. Hoffelner  et al.

Journal of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2012.11.031.

Effect of ion-irradiation on the microstructure and microhardness of the W-2Y(2)O(3) composite materials fabricated by sintering and hot forging

M. BattabyalP. SpätigN. Baluc

2013. 27th Symposium on Fusion Technology (SOFT). p. 1668 - 1672. DOI : 10.1016/j.fusengdes.2013.03.060.

Effect of warm pre-stressing on fracture toughness of Eurofer97 steel

N. IlchukL. ComminP. SpätigG. R. Odette

2013. 27th Symposium on Fusion Technology (SOFT), Liège, Belgium, September 24-28, 2012. p. 644 - 647. DOI : 10.1016/j.fusengdes.2013.05.056.

Creep Properties and Related Microstructural Changes of a Lamellar Titanium Aluminide Alloy before and after Helium-Implantation

P. Magnusson

Lausanne, EPFL, 2012. DOI : 10.5075/epfl-thesis-5306.

W-2 wt.%Y2O3 composite: Microstructure and mechanical properties

M. BattabyalR. SchäublinP. SpätigB. Baluc

Materials Science and Engineering: A. 2012. DOI : 10.1016/j.msea.2012.01.011.

Nanocomposites of carbon nanotubes embedded in a (Ti,Al)N coated film

L. MarotT. de los ArcosA. BünzliC. WäckerlinR. Steiner  et al.

Surface and Coatings Technology. 2012. DOI : 10.1016/j.surfcoat.2012.09.053.

Effect of thermo-mechanical treatments on the microstructure and mechanical properties of an ODS ferritic steel

Z. OksiutaP. MuellerP. SpätigN. Baluc

Journal of Nuclear Materials. 2011. DOI : 10.1016/j.jnucmat.2011.03.006.

From materials development to their test in IFMIF: an overview

N. BalucR. SchäublinP. SpätigN. llchukL. Veleva  et al.

Nuclear Fusion. 2011. DOI : 10.1088/0029-5515/51/11/113006.

Strain-rate behavior in tension of the tempered martensitic reduced activation steel Eurofer97

E. CadoniM. DottaD. ForniP. Spätig

Journal Of Nuclear Materials. 2011. DOI : 10.1016/j.jnucmat.2011.05.002.

From Materials Development to their Test in IFMIF: an Overview

N. BalucR. SchäublinP. SpätigJ. TheileM.-Q. Tran

2010. 23rd IAEA Fusion Energy Conference, Daejon, Korea, 11-16 October 2010.

Recent progress toward development of reduced activation ferritic/martensitic steels for fusion applications

R. J. KurtzA. AlamoE. LuconQ. HuangS. Jitsukawa  et al.

2009. 13th International Conference on Fusion Reactor Materials, Nice, France, December 10-14, 2007. p. 411 - 417. DOI : 10.1016/j.jnucmat.2008.12.323.

Finite element modeling and experimental study of brittle fracture in tempered martensitic steels for thermonuclear fusion applications

P. F. Mueller

Lausanne, EPFL, 2009. DOI : 10.5075/epfl-thesis-4518.

Numerical investigation by finite element simulations of the ball punch test: Application to tempered martensitic steels

E. CampitelliP. SpätigJ. Bertsch

2009. 13th International Conference on Fusion Reactor Materials, Nice, France, December 10-14, 2007. p. 319 - 322. DOI : 10.1016/j.jnucmat.2008.12.120.

Fracture toughness master-curve analysis of the tempered martensitic steel Eurofer97

P. MuellerP. SpätigR. BonadéG. R. OdetteD. Gragg

2009. 13th International Conference on Fusion Reactor Materials (ICFRM-13), Nice, France, December 10-14, 2007. p. 323 - 327. DOI : 10.1016/j.jnucmat.2008.12.122.

Assessment of irradiation embrittlement of the Eurofer97 steel after 590 MeV proton irradiation

P. SpätigR. StoenescuP. MuellerG. R. OdetteD. Gragg

2009. 13th International Conference on Fusion Reactor Materials, Nice, France, December 10-14, 2007. p. 245 - 248. DOI : 10.1016/j.jnucmat.2008.12.110.

3D finite element and experimental study of the size requirements for measuring toughness on tempered martensitic steels

P. MuellerP. Spätig

Journal of Nuclear Materials. 2009. DOI : 10.1016/j.jnucmat.2009.01.311.

A multiscale approach to measuring and modeling cleavage fracture in structural steels

G. R. OdetteH. J. RathbunM. HribernickT. YamamotoM. He  et al.

Materials Issues for Generation IV Systems; Dordrecht, The Netherlands: Springer, 2008. p. 203 - 226.

The evolution of the mobile dislocation density during successive stress relaxation transients

R. BonadéP. Spätig

Materials Science and Engineering: A. 2008. DOI : 10.1016/j.msea.2006.10.196.

Fracture properties of notched and pre-cracked specimens of a tempered martensitic steel at low temperature

P. MuellerR. BonadeP. Spätig

2008. 14th International Conference on the Strength of Materials (ICSMA 14), Xian, PEOPLES R CHINA, June 4-9, 2006. p. 346 - 349. DOI : 10.1016/j.msea.2006.09.172.

Fracture toughness behavior in the ductile-brittle transition region of the tempered martensitic Eurofer97 steel: Experiments and modeling

R. BonadéP. MuellerP. Spätig

Engineering fracture mechanics. 2008. DOI : 10.1016/j.engfracmech.2008.01.016.

Analysis of high temperature deformation mechanism in ODS EUROFER97 alloy

A. RamarP. SpätigR. Schaeublin

2008. Symposium on Microstructural Processes in Irradiated Materials held at the 2007 TMS Annual Meeting, Orlando, FL, USA, February 25 - March 1, 2007. p. 210 - 216. DOI : 10.1016/j.jnucmat.2008.08.009.

Measurement of the effective activation volume in 45 XD titanium aluminides by repeated transient tests

F. DiologentT. Kruml

Materials Science and Engineering: A. 2008. DOI : 10.1016/j.msea.2007.10.029.

Fracture toughness properties in the transition region of the Eurofer97 tempered martensitic steel

R. BonadeP. SpätigN. Baluc

Journal of Nuclear Materials. 2007. DOI : 10.1016/j.jnucmat.2007.03.031.

The role of small specimen test technology in fusion materials development

G. E. LucasG. R. OdetteH. MatsuiA. MöslangP. Spätig  et al.

Journal of Nuclear Materials. 2007. DOI : 10.1016/j.jnucmat.2007.04.034.

Plastic flow properties and fracture toughness characterization of unirradiated and irradiated tempered martensitic steels

P. SpätigR. BonadeG. R. OdetteJ. W. RensmanE. N. Campitelli  et al.

Journal of Nuclear Materials. 2007. DOI : 10.1016/j.jnucmat.2007.03.038.

The European effort towards the development of a demo structural material: Irradiation behaviour of the European reference RAFM steel EUROFER

E. LuconP. BenoitP. JacquetE. DiegeleR. Lasser  et al.

Fusion Engineering and Design. 2006. DOI : 10.1016/j.fusengdes.2005.08.044.

Constitutive behavior and fracture properties of tempered martensitic steels for nuclear applications : experiments and modelling

R. A. Bonadé

Lausanne, EPFL, 2006. DOI : 10.5075/epfl-thesis-3405.

Assessment of plastic flow and fracture properties with small specimen test techniques for IFMIF-designed specimens

P. SpätigE. N. CampitelliR. BonadéN. Baluc

Nuclear Fusion. 2005. DOI : 10.1088/0029-5515/45/7/011.

Assessment of irradiation-hardening on Eurofer97' and Zircaloy 2 with punch tests and finite-element modeling

E. N. CampitelliP. SpätigJ. BertschC. Hellwig

Materials Science and Engineering: A. 2005. DOI : 10.1016/j.msea.2005.02.088.

Deformation behaviour and microstructure of nanocrystalline electrodeposited and high pressure torsioned nickel

F. Dalla TorreP. SpätigR. SchäublinM. Victoria

Acta Materialia. 2005. DOI : 10.1016/j.actamat.2005.01.041.

The relationship between the irradiation induced damage and the mechanical properties of single crystal Ni

Z. Yao

Lausanne, EPFL, 2005. DOI : 10.5075/epfl-thesis-3177.

Mechanical behaviour of nanocrystalline electrodeposited Ni above room temperature

F. Dalla TorreH. Van SwygenhovenR. SchäublinP. SpätigM. Victoria

Scripta Materialia. 2005. DOI : 10.1016/j.scriptamat.2005.03.026.

Dislocation defect interaction in irradiated Cu

R. SchäublinZ. YaoP. SpätigM. Victoria

Materials Science and Engineering: A. 2005. DOI : 10.1016/j.msea.2005.03.093.

On the strain-hardening of tempered martensitic alloys

R. BonadéP. Spätig

Materials Science and Engineering: A. 2005. DOI : 10.1016/j.msea.2004.12.056.

Assessment of mechanical properties in unirradiated and irradiated zircaloys and steels with non-standard tests and finite element calculations

E. Campitelli

Lausanne, EPFL, 2005. DOI : 10.5075/epfl-thesis-3304.

The tensile properties of irradiated Ni single crystals and their temperature dependence

Z. YaoR. SchäublinP. Spätig

Philosophical Magazine. 2005. DOI : 10.1080/14786430412331319947.

Assessment of the constitutive properties from small ball punch test: experiment and modeling

E. N. CampitelliP. SpätigR. BonadéW. HoffellnerM. Victoria

Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.07.052.

Hardening mechanisms in ferritic/martensitic steels

M. L. GrossbeckT. R. AllenR. G. LottA. S. KumarN. Baluc  et al.

2004. Effects of radiation on materials, Tucson, June 18-20, 2002. p. 341 - 351.

Tensile properties of a tempered martensitic iron-chromium- carbon model alloy

R. BonadéP. SpätigM. VictoriaT. YamamotoG. R. Odette

Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.054.

A master curve analysis of F82H using statistical and constraint loss size adjustments of small specimen data

G. OdetteT. YamamotoH. KishimotoM. SokolovP. Spätig  et al.

Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.255.

Materials design data for reduced activation martensitic steel type EUROFER

A. A. F. TavassoliA. AlamoL. BedelL. ForestJ. M. Gentzbittel  et al.

Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.020.

SANS investigation of proton-irradiated EUROFER97

P. SpätigR. SchäublinN. BalucJ. KohlbrecherM. Victoria

Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.052.

On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactors

N. BalucR. SchäublinP. SpätigM. Victoria

Nuclear Fusion. 2004. DOI : 10.1088/0029-5515/44/1/006.

Plastic flow of martensitic model alloys

R. BonadéP. SpätigR. SchäublinM. Victoria

Materials Science and Engineering: A. 2004. DOI : 10.1016/j.msea.2004.02.074.

Second IEA fusion materials agreement workshop on modeling and experimental validation

M. VictoriaP. Spätig

Journal of Nuclear Materials. 2003. DOI : 10.1016/j.jnucmat.2003.08.017.

Second IEA Fusion Materials Agreement Workshop - Proceedings of the Second IEA Fusion Materials Agreement Workshop on Modeling and Experimental Validation - Les Diableret, Switzerland - September 30-October 4, 2002 - Preface

M. VictoriaP. Spätig

Journal of Nuclear Materials. 2003. DOI : 10.1016/j.jnucmat.2003.08.016.

Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H

S. JitsukawaM. TamuraB. van der SchaafR. KluehA. Alamo  et al.

Journal of Nuclear Materials. 2002. DOI : 10.1016/S0022-3115(02)01075-9.

Enseignement et PhD

Doctorant·es actuel·les

Rémi Martinie, Gabriel Artus Benedikt Brinkmann

A dirigé les thèses EPFL de

Emiliano Campitelli, Raul Alejandro Bonadé, Pablo Federico Mueller, Per Magnusson, Nazar Ilchuk, Anna Prokhodtseva, Christiane Vieh, Kun Wang, Ignasi Villacampa Roses, Serafin Knitel, Zaiqing Que, Elvis Fornasiere, Wen Chen, Elif Cansu Kursun, Puyi Gao, Dongyang Jiang

Cours

Advanced topics in nuclear reactor materials

ETH-530

Comprendre les aspects avancés de sciences des matériaux en application à l'énergie nucléaire (fission et fusion). Se familiariser avec les matériaux pour des centrales modernes, la caractérisation avancée des dommages et évaluation de durée de vie